L-83-507, Forwards Response to NRC Concerns Discussed in 830815 Telcon Re Tech Spec Changes to F Delta H Limit.Impact of Change Limited to Expected cycle-wide Power Distribution Differences
| ML17345B295 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/04/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-83-507, NUDOCS 8310110296 | |
| Download: ML17345B295 (12) | |
Text
REGULATORY +FORMATION OISTRISUTION SY+M (RIOS)
ACCESSION NBR:8310110296 DOC ~ OATEN'3/10/04 NOTARI'ZED~
NO DOCKET FACIL':50 250 Turkey Point Planti Unit 3i Florida, Power and Light C
05000250
'50 251 Tur key Point Pl anti Unit 4i Fl or ida Power and light C
05000251 AUTH'AME AUTHOR AFFILIATION UHRIGi R ~ E ~
Florida Power L Light Co, RECIP ~ NAME RECIPIENT AFFILIATION EISENHUTiDGG.
Division of Licensing
SUBJECT:
Forwards response to NRC concerns discussed in 830815 telcon re Tech Spec changes to F delta H limit~ Impact of change limited to expected cycle-wise power distribution differences, DISTRIBUTION CODE:
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BOX 14000, JUNO BEACH, FL 33408 FLORIDA POWER 8 LIGHTCOMPANY October 4, I 983 L-83-507 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear 'Mr. Eisenhut:
Re:
Turkey Point Units 3 & 4 Docket Nos. 50-250 & 50-25 I Clarification to F H/FQ Technical'S ecification Chan es Attachment I contains FPL's responses to concerns discussed with your staff on an August l5, l 983 telecon.
If there are any further concerns please contact us.
Very truly yours, ert E. Uhrig Vice President Advanced Systems & Technology REU/SAV/cab Attachment cc:
J. P. O'Reil ly, Region II Harold F. Reis, Esquire 8310110296 831004 PDR ADOCK 05000250 P
PDR PEOPLE... SERVING PEOPLE
ATTACHMENT 1 Question 1:
How does the CAOC power distribution control strategy apply to a pHR with an increased F delta H limit of 1.62 (1
+ 0.3 (1-P))?
Response
The CAOC operating strategy in effect at Turkey point will continue to provide the same level of protection with an increased F-delta-H limit as in previous cycles with a lower F-delta-H limit as discussed in Reference 1.
The primary focus of the CAOC operating strategy is directed at assurance that gWZ) is bounded within the limits defined by the LOCA analysis.
As discussed in References 1 and 2, the FAC analysis is used to provide assurance that a given core design will not exceed the LOCA FQ limit for load follow maneuvers allowed within the plant technical specifications.
The FAC analysis methodology as described in References f and 2 continues to apply for PWR cores with elevated F-delta-H limits.
Reference 1
specifies the conditions under which the verification that the LOCA FQ limit is generically assured and no calculations need be performed.
These conditions are:
1.
The allowed ~I band is no wider than
+5%6I.
2.
The LOCA FQ limit is greater than or equal to 2.32.
3.
The F-delta-H limit is F
~
< 1.55 (1
+ 0.2 (1-P)).
aH The proposed technical specification changes fall outside of the conditions specified above.
Therefore, the FAC analysis has been and will continue to be performed to assure that the FQ limit is not exceeded by the methodology defined in Ref.
1 for upcoming reloads at Turkey Point.
The results of the FAC analysis for the Turkey Point Unit 3, Cycle 9
core are attached to this discussion.
The attached analysis and future analysis have been or will be performed as. outlined in Reference 2.
The FAC analysis utilizes a 1D/3D synthesis of 1D axial simulated load follow power shapes and 3D elevation dependent radial peaking factors.
The 1D simulation is sensitive to burnup distribution, control rod insertion limits, core power density, CVCS capability, and load follow strategy of the 'eactor under study.
Very localized radial peaking (Fxy) has no effect on the core average axial power distribution P(Z) but directly impacts the total heat flux peaking factor, FQ.
The proposed F-delta-H limit increase will be accounted for in the Fxy(Z) which is us d in the analyses.
FAC analyses with the increased F-delta-H limit are performed with methods consistent with Reference 2.
q
Question 2-What is the impact on operating cycles of changing the F-delta-H and FQ limits?
- Response
This has no impact on current operating cycles because they were designed with the lower limits.
Question 3:
What is the impact of the proposed F-delta-H limit increase on the current Baseload and Radial Burndown technical specifications?
Response
The surveillance function of the current Baseload and Radial Burndown technical specifications are unaffected by the proposed technical specification changes.
The methodology that provides input to the INCORE measurement system remains unchanged.
Therefore, the impact of this proposed technical specification change is limited to expected cycle-wise power distribution differences.
- Further, because the methodology utilized in generating the INCORE measurement constants and the appli;cation of these measurement constants to process moveable detector flux traces remains unchanged, the measurement uncertainties associated with power distribution measurement
.are unaffected.,
The stated FQ and F-delta-H limits in,these technical specifications will be changed to reflect the higher limits.
0
REFERENCES 1.
Morita, T., et al, "Power Distribution Control and Load Follow Procedures,"
WCAP-8385 (Proprietary) and WCAP-8403 (Non-Proprietary),
September,1974.
2.
Borderlon, F. M., et al, "Westinghouse Reload Safety Evaluation Methodology,",,
WCAP-9272 (Proprietary),
March 1978.
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- i. 48 LOCA ENVELOPE CYCLE 9 VALUES
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